... or other incidents. This paper summarizes a two-year EPRI project to evaluate the effects of chloride and sulfate transients at 5 ppb, 20 ppb, and 100 ppb on the SCC growth behavior of cold-worked austenitic stainless steel and as-welded nickel-base Alloy 182 in boiling water reactor (BWR) normal water...

... measure of SCC susceptibility under ppb level of chloride. The result from this program suggests that the chloride level as low as 2-4 ppb can increase the SCC susceptibility of low alloy steel in BWR environment. pressure vessel steel A533B stress corrosion cracking chloride boiling water reactor...

...Abstract Hydrogen peroxide (H₂O₂) is the most important oxidant to determine the corrosive environment of boiling water reactors (BWRs). Since H₂O₂ is unstable at high temperature and electrochemical measurement in high purity water is difficult...

...Abstract Stress corrosion cracking (SCC) has been occurred in boiling water reactor (BWR) components, such as reactor core shrouds and primary loop recirculation (PLR) pipes made of L-grade austenitic stainless steels, which are not thermally sensitized. SCC of reactor core shrouds and PLR pipes...

... of Type 316L SS. The surface hardened layer increased SCC susceptibility and shortened the incubation time. Boiling Water Reactor Stainless Steel Stress Corrosion Cracking High Temperature Water Creviced Bent Beam Method INTRODUCTION Boiling water reactors (BWR) have been operating for more than 35...

... water reactor noble metal yittria-stabilized zirconia high temperature water plasma spray INTRODUCTION IGSCC of sensitized SS components in boiling water reactors (BWRs) is known to be a major concern [ 1 , 2 ]. The IGSCC susceptibility of structural materials in BWRs is influenced by the ECP (see...

... on cooperative confirmatory research, as discussed further below. Voluntary Industry Initiatives Abstract The regulatory issues associated with cracking of boiling water reactor (BWR) internals is being addressed by the Nuclear Regulatory Commission (NRC) staff and is the subject of a voluntary industry...

...IGSCC of sensitized SS components in boiling water reactors (BWRs) is known to be a major concern[ 1 - 5 ]. The IGSCC susceptibility of strucutral materials in BWRs is influenced by the ECP (see Figure 1 ), which is controlled by the amounts of oxidizing and reducing species and the hydrodynamic...

... that the corrosion potential of YSZ coated 304 SS remained at ≈ -0.5 V_she in 288°C water containing up to 200 ppb O₂ and no H₂. Corrosion potential insulated coatings boiling water reactor yttria stablized zirconia high temperature water plasma spray INTRODUCTION The coolant...

...Abstract In recent years much attention has been focused on the use of hydrogen water chemistry (HWC) to control the electrochemical corrosion potential (ECP) of stainless steel in boiling water reactors (BWRs) to mitigate intergranular stress corrosion cracking (IGSCC) of sensitized 304 stainless...

... the responses of Dresden-2 and Duane Arnold boiling water reactors (BWRs) to hydrogen water chemistry (HWC) with the application of general catalysis (increasing the exchange current density) and general inhibition (decreasing the exchange current density). HWC simulations for these two BWRs were carried out...

... to be indifferent to both the operating power level and the feedwater hydrogen concentration. boiling water reactor IGSCC hydrogen water chemistry power level ECP crack growth rate INTRODUCTION Hydrogen water chemistry (HWC) has been shown to be effective in mitigating intergranular stress corrosion cracking...

... flow exposure caused some loss of noble metals and thereby shifted the corrosion potential in the positive direction. corrosion potential catalytic property 304 SS noble metals high temperature water boiling water reactor INTRODUCTION The coolant in boiling water reactor (BWR) recirculation lines...

...Abstract The limited accessibility of boiling water reactors (BWRs) has made it difficult or sometimes impossible to monitor the development of material damage inside these reactors. Material damage in BWRs usually occurs in the form of intergranular stress corrosion cracking (IGSCC...

...noble metal chemical addition electrochemical corrosion potential crack initiation crack propagation boiling water reactor nuclear materials INTRODUCTION The concept of achieving lower ECPs at relatively low hydrogen levels by having a thin platinum coating electrolessly deposited on 316 SS...

...-irradiation hardness. Stress-corrosion resistance was measured in constant extension rate tensile (CERT) and constant deflection tests. The effectiveness of a given LTA treatment was found to depend on the type of SCC test. bent beams boiling water reactor constant deflection constant extension rate...

... high-purity water boiling water reactor interdendritic stress-corrosion cracking corrosion pits INTRODUCTION It is well known that sensitized Type 304 stainless steels are susceptible to stress- corrosion cracking in the boiling water reactor (BWR) primary coolant environment, i.e., a high...

..., of which Alloy 600 is representative, exhibit often enough susceptibility to intergranular stress-corrosion cracking in laboratory acceleration tests conducted under conditions to simulate the boiling water reactor (BWR) environments ^{1 - 3} . Furthermore, several cases of stress-corrosion...

...Abstract An algorithm for assessing, theoretically, the effectiveness of hydrogen water chemistry (HWC) in Boiling Water Reactors (BWRs) is described. The algorithm, DAMAGE-PREDICTOR, contains facilities for estimating the concentrations of radiolysis products (in particular O₂...

... in the lower plenum region are also estimated in a preliminary way. boiling water reactor hydrogen water chemistry intergranular stress corrosion cracking stainless steel water radiolysis modeling INTRODUCTION Boiling Water Reactors (BWRs) use high purity water as the neutron moderator and primary coolant...